2017•Annals of Nuclear EnergyRequires access

Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations

Shengcheng Zhou, Won Sik Yang, Tongkyu Park, Hongchun Wu

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Key concepts: Neutron transport, Molten salt, Molten salt reactor, Nuclear engineering, Delayed neutron, Spent nuclear fuel, Thermal hydraulics, Nuclide

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Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations — Research Paper | ScholarLens